Published 1989
| Version v1
Journal article
Confinement scaling studies in DIII-D
Description
Understanding and increasing the energy confinement time (τE ≡ W/P) remains a primary goal of fusion research. This objective is being pursued on DIII-D via investigations of τE in limiter and single- and double-null divertor discharges with Ohmic heating and neutral beam heating. This paper examines the dependence of τE on ion mass, plasma current (Ip), neutral beam power (Pb), toroidal field (BT), and safety factor (q). The data presented is for neutral beam injection in the direction of the plasma current, although τE is the same for both co- and counter-injection. (author) 12 refs., 5 figs
Additional details
Publishing Information
- Journal Title
- Europhysics Conference Abstracts
- Journal Volume
- 13B
- Series
- Europhys. Conf. Abstr.
- Journal Page Range
- 115-118
- ISSN
- 0378-2271
- CODEN
- ECABD
Conference
- Title
- 16. European conference on controlled fusion and plasma physics.
- Dates
- 13-17 Mar 1989.
- Place
- Venice (Italy).
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 20073455
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CONFINEMENT TIME; EXPERIMENTAL DATA; H-MODE PLASMA CONFINEMENT; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; DATA; INFORMATION; NUMERICAL DATA; PLASMA CONFINEMENT; THERMONUCLEAR DEVICES